TRAC-BF1/MOD1: An advanced best-estimate computer program for BWR accident analysis, Model description. Volume 1
TRAC-BF1/MOD1: An advanced best-estimate computer program for BWR accident analysis, Model description. Volume 1
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TRAC-BF1/MOD1：用于沸水堆事故分析的先进最佳估计计算机程序，模型描述。
DOI：
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发表时间：
1992
期刊：
影响因子：
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通讯作者：
W. Weaver
中科院分区：
文献类型：
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作者：
J. Borkowski;N. L. Wade;M. Giles;S. Rouhani;R. Shumway;G. Singer;D. Taylor;W. Weaver
爱达荷州国家工程实验室的TRAC-BWR代码开发计划已经为美国核管理委员会和公众开发了瞬态反应堆分析代码（TRAC）的版本。TRAC-BF 1/MOD 1版本的计算机代码提供了一个最佳估计分析能力，用于分析沸水堆（BWR）系统和相关设施的假设事故的全部范围。该版本提供了一致和统一的分析能力，用于分析大型或小型冷却剂损失事故（LOCA）的所有领域，从排污阶段开始，继续进行加热，淬火再冷却，最后是事故的再填充阶段。还提供了分析运行瞬态（包括预期瞬态）的基本能力，而无需紧急停堆（ATWS）。TRAC-BF 1/MODI版本产生的结果与以前的版本一致。使用两个TRAC-BF 1版本的评估计算表明，与早期版本的TRAC-BWR系列计算机代码相比，在数据一致性和计算时间方面有了全面改进。
The TRAC-BWR code development program at the Idaho National Engineering Laboratory has developed versions of the Transient Reactor Analysis Code (TRAC) for the US Nuclear Regulatory Commission and the public. The TRAC-BF1/MODl version of the computer code provides a best-estimate analysis capability for analyzing the full range of postulated accidents in boiling water reactor (BWR) systems and related facilities. This version provides a consistent and unified analysis capability for analyzing all areas of a large- or small-break loss-of-coolant accident (LOCA), beginning with the blowdown phase and continuing through heatup, reflood with quenching, and, finally, the refill phase of the accident. Also provided is a basic capability for the analysis of operational transients up to and including anticipated transients without scram (ATWS). The TRAC-BF1/MODI version produces results consistent with previous versions. Assessment calculations using the two TRAC-BF1 versions show overall improvements in agreement with data and computation times as compared to earlier versions of the TRAC-BWR series of computer codes.